ML20073L031
| ML20073L031 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/06/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073L021 | List: |
| References | |
| NUDOCS 9105130168 | |
| Download: ML20073L031 (3) | |
Text
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NUCLEAR REGULATORY COMMISSION
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REL ATED TO AMENDMENT NO.153 TO FACILITY OPERATING LICENSE NO. OPR-53 AND AMENOMENT NO.133 TO F ACILITY OPERATING LICENSE NO. OPR-69 BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318
1.0 INTRODUCTION
By letter dated March 7, 1991, Baltimore Gas and Electric Company (the licensee) submitted a request for changes to the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Technical Specifications (TSs).
The requested changes would revise the TSs for Unit 2 to require that the Safety Injection Tanks (SITS) be operable throughout Mode 3.
The Unit 1 TSs already include this requirement.
The amendments also would revise the TSs surveillance requireTents for the SITS of both Units 1 and 2 to be consistent with the operability requirements during Mode 3 operation, provides editorial changes to the applicable TSs titles to accurately reflect the amendment changes, and the Index and Bases Sections are updated to reflect the changes in the operability and surveillance requirements.
2.0 EVALUATION The safety injection tanks (SITS) provide water to begin the re-flooding of the core following a reactor coolant system (RCS) blowdown to minimize core damage until the safety injection pumps can provide adequate water for reactor cooling.
The tanks are designed to inject large quantities of borated water into the RCS immediately following a large pipe break, in such an event, the water begins to re-flood and cool the core, thereby limiting clao-heatup and metal-water reaction until the safety injection pump flows are established.
During normal pressure and temperature operating conditions, TS 3.5.1 ensures that the SITS are available to perform this function.
The current Unit 2 TS 3.5.1 does not require the SITS to be operable for all of Mode 3.
The SITS are only required to be operable when pressures are equal to or greater than 1750
- psia, 01051201 M 910506 DR ADOE 0500 7
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Previous TS changes have imposed restrictions on the high pressure safety injection (HPSI) pumps when operating in Mode 3 These restrictions are necessary to protect against overpressure events due to mass addition transients.
The operability of the SITS through the entire mode is necessary to assure mitication of a lors-of-coolant accident (LOCA) due to the restrictions placed on the HPSI pumps.
This operability requirement has been previously reviewed and approved by the NRC staff for Unit 1.
The licensee provided the results of a postulated LOCA analysis to determine the SITS pressure and volume needed to fill the reactor vessel following a large break LOCA and the minimum tine available to initiate additional RCS makeup flow to maintain core heat removal.
The results of the licensee's analysis indicates that there is at least 18 minutes available for the operators to identify the plant conditions and take appropriate action to initiate additional RCS makeup flow.
The licensee also identified the procedure used, Abnormal Operating Procedures (A0P)-2A, " Excessive Reactor Coolant Leakage," which specifies the operator actions necessary to mitigate the consecuences of both small and large break LOCAs.
The staff has determined, based on the details discussed above and its previous safety evaluation in support of Amendment No.140 to the Unit 1 Operating License, dated March 6,1990, that the analysis performed supports the capability of the SITS to mitigate a LOCA during Mode 3 operation with the existing HPSI pump restrictions.
Therefore, the requirement to have the SITS operable during the entire Mode 3 for Unit 2 is consistent with that previously approved for Unit 1 and is acceptable.
The current TSs require that the isolation valves for each SIT be verified i
opened within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to increasing the RCS pressure greater than 1750 osia.
The requested change requires that the verification be performed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to entering Mode 3, regardless of the pressure, to assure the SITS availability during the entire Mode 3 operation.
The staff has determined that the requested surveillance requirements will provide assurance that the SITS will meet their operability requirements prior to entering Mode 3 for both Units 1 and 2 and are, therefore, acceptable.
The title changes are proposed to accurately reflect the required Limiting Condition For Operation (LCO) of Emergency Core Cooling Systems for operation equal to or greater than 1750 psia (TS 3.5.2) and for operation less than 1750 psia (TS 3.5.2).
The licensee has indicated, and the staff agrees, that the changes more closely reflect the applicable operational conditions of the TSs for which they are provided.
The staff, therefore, has determined that the title changes are acceptable.
The Index and Bases Sections are updated to reflect those changes discussed above and are acceptable.
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,$,T ATE _ CONSULT ATION in accordance with the Cornission's regulations, the Maryland St ate official was notified of the proposed issuance of the anendtrents.
The State official had no corir;ents.
4.0 ENVIR0tWENTAL CONSIDERAT10tl The amendnents change to a requirerent with respect to installation or use of a facility corponent located within the restricted area as defined in 10 CFR Part 20, and changes to the surveillence requirements.
The NFC staff has determined that the aneridnents involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or curuulative occupational radiation esposure.
The Concission has previously issud a proposed finding that the armendnents involve no sign 111 cant hazards corisideration, and there has be(n no p"blic cornnent on such finding (E0 FR 13658). Accordingly, the arnendnents rneet the eligibility criteria for categorical cyclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environnental inpact statenent or environn. ental assessment need be prepared in connection with the issuance of the amendnents.
5.0 CONCLUSION
The Cornistion has concluded, based on the considerations discussed above, that:
(.1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in conpliance with the Cornistion's regulations, and (3) the issvence of the amendn'ents will not be inimical to the conmon defense and security or to the health and saf ety of the public.
Principal Contributor:
Daniel G. Mcdonald Date: May 6, 1991
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Docket Nos. 50 317 Miy 6,1991 and 50 316 Mr. G. C. Creel Vice President. Nuclear Energy Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant MD Rts. 2 & 4 P. O. Box 1535 Lusby, Maryland 20657
Dear Mr. Creel:
SUBJECT:
ISSUANCE OF AMENDMENTS FOR CALVERT Cl.!FFS NUCLEAR POWER PLANT, UNIT NO. 1 (TAC NO. 79994) AND UNIT NO. 2 (TAC NO. 79995)
The Commission has issued the enclosed Amendment No.153to f acility Operating License No. DPR.53 and Amendment No.133 to f acility Operating License No.
DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2, respec-tively. The amendments consist of changes to the Technical Specifications in response to your application transmitted by letter dated March 7,1991.
The emendments change the Technical Specifications (TS$) for Unit 2 to reaufre that the Safety injection Tanks (SITS) be operable throughout Mode 3.
The Unit 1 TSs already include this requirement.
The amendments also revise the TSs surveillance requirements for the SITS of both Units 1 and 2 to be consistent with the operability requirements during Mode 3 operation, includes editorial changes to the applicable TSs titles to accurately reflect the amendment changes, and the Index and Beses Sections are updated to reflect the changes in the operability and surveillance requirements.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Reaister notice.
Sincerely, ORIGINAL $1GNED BY Daniel G. Mcdonald, Senior Project Manager Project Directorate 1 1 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendment No.153to DPR.53 2.
Amendment No.133to DPR.69 3.
Safety Evaluation cc w/ enclosures:
See next page n
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Document Name:
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Docket File NRC/ Local PDRs PDI-l Readino
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